Microstructural evolution of cast austenitic stainless steels under accelerated thermal aging

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Abstract

Thermal aging degradation of cast austenitic stainless steels (CASS) was studied by electron microscopy to understand the mechanisms for thermal embrittlement potentially experienced during extended operations of light water reactor coolant systems. Four CASS alloys—CF3, CF3M, CF8, and CF8M—were thermally aged up 1500 h at 330 and 400 °C, and the microstructural evolution of the material was characterized by analytical aberration-corrected scanning transmission electron microscopy. The primary microstructural and compositional changes during thermal aging were spinodal decomposition of the δ-ferrite into α/α′, precipitation of G-phase in the δ-ferrite, segregation of solute to the austenite/ferrite interphase boundary, and growth of M 23 C 6 carbides on the austenite/ferrite interphase boundary. These changes were shown to be highly dependent on aging temperature and chemical composition, particularly the amount of C and Mo. A comprehensive model is being developed to correlate the microstructural evolution with mechanical behavior and simulation.

Original languageEnglish
Title of host publicationMinerals, Metals and Materials Series
PublisherSpringer International Publishing
Pages1859-1868
Number of pages10
ISBN (Print)9783030046385, 9783030046392, 9783319515403, 9783319651354, 9783319728520, 9783319950211
DOIs
StatePublished - 2019
Externally publishedYes
Event18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2019 - Boston, United States
Duration: Aug 18 2019Aug 22 2019

Publication series

NameMinerals, Metals and Materials Series
ISSN (Print)2367-1181
ISSN (Electronic)2367-1696

Conference

Conference18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2019
Country/TerritoryUnited States
CityBoston
Period08/18/1908/22/19

Funding

This research was sponsored by U.S. Department of Energy/Office of Nuclear Energy through Light Water Reactor Sustainability R&D Program and International Nuclear Energy Research Initiative (I-NERI) Program. Pacific Northwest National Laboratory is operated by Battelle Memorial Institute for the U.S. Department of Energy under Contract No. DEAC05-76RL01830. APT and FIB/SEM were performed at PNNL’s Environmental Molecular Sciences Laboratory, a Department of Energy—Office of Biological & Environmental Research national scientific user facility.

FundersFunder number
I-NERI
Light Water Reactor Sustainability R&D Program and International Nuclear Energy Research Initiative
U.S. Department of EnergyDEAC05-76RL01830
Battelle
Office of Nuclear Energy

    Keywords

    • Duplex stainless steel
    • G-phase precipitation
    • Solute segregation
    • Spinodal decomposition
    • Thermal aging degradation

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